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| | issue date = 09/19/1983 | | | issue date = 09/19/1983 |
| | title = NRC Generic Letter 1983-031: Safety Evaluation of Abnormal Transient Operating Guidelines. | | | title = NRC Generic Letter 1983-031: Safety Evaluation of Abnormal Transient Operating Guidelines. |
| | author name = Eisenhut D G | | | author name = Eisenhut D |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
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Category:NRC Generic Letter
MONTHYEARNRC Generic Letter 1999-021999-08-23023 August 1999 NRC Generic Letter 1999-002: (Errata): Laboratory Testing of Nuclear-Grade Activated Charcoal NRC Generic Letter 1983-111999-06-24024 June 1999 NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis ML0823509351999-06-0303 June 1999 Generic Ltr 99-02 to All Holders of OLs for Nuclear Power Reactors,Except Those Who Have Permanenetly Ceased Operations & Certified That Fuel Permanently Removed from Rv Re Laboratory Testing of nuclear-grade Activated Charcoal ML0311101371999-06-0303 June 1999 Withdrawn NRC Administrative Letter 1999-002: Operating Reactor Licensing Action Estimates NRC Generic Letter 1999-011999-05-0303 May 1999 NRC Generic Letter 1999-001: Recent Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities NRC Generic Letter 1998-011999-01-14014 January 1999 NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants ML0311101601998-08-0303 August 1998 Withdrawn NRC Administrative Letter 1998-005: Availability of Summaries in Electronic Format of Technical Reports by Office for Analysis & Evaluation of Operational Data NRC Generic Letter 1998-041998-07-14014 July 1998 NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i NRC Generic Letter 1998-021998-05-28028 May 1998 NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition NRC Generic Letter 1997-061997-12-30030 December 1997 NRC Generic Letter 1997-006: Degradation of Steam Generator Internals NRC Generic Letter 1997-051997-12-17017 December 1997 NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques NRC Generic Letter 1996-061997-11-13013 November 1997 NRC Generic Letter 1996-006, Supplement 1: Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions ML0312007011997-10-0808 October 1997 Withdrawn NRC Generic Letter 1991-018, Revision 1: Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions NRC Generic Letter 1997-041997-09-30030 September 1997 NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules NRC Generic Letter 1997-031997-07-0909 July 1997 NRC Generic Letter 1997-003: Annual Financial Surety Update Requirements for Uranium Recovery Licensees NRC Generic Letter 1997-021997-05-15015 May 1997 NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report NRC Generic Letter 1995-061997-01-31031 January 1997 NRC Generic Letter 1995-006: Changes in Operator Licensing Program NRC Generic Letter 1996-081996-12-15015 December 1996 NRC Generic Letter 1996-008: Interim Guidance on Transportation of Steam Generators NRC Generic Letter 1996-051996-09-18018 September 1996 NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves NRC Generic Letter 1996-041996-06-26026 June 1996 NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks NRC Generic Letter 1995-091996-04-0505 April 1996 NRC Generic Letter 1995-009: Supplement 1: Monitoring and Training of Shippers and Carriers of Radioactive Materials NRC Generic Letter 1996-021996-02-13013 February 1996 NRC Generic Letter 1996-002: Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat NRC Generic Letter 1996-031996-01-31031 January 1996 NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits NRC Generic Letter 1989-101996-01-24024 January 1996 NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors NRC Generic Letter 1996-011996-01-10010 January 1996 NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits NRC Generic Letter 1995-101995-12-15015 December 1995 NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation ML0310701501995-10-31031 October 1995 Withdrawn - NRC Generic Letter 1995-008: 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval NRC Generic Letter 1993-031995-10-20020 October 1995 NRC Generic Letter 1993-003: Verification of Plant Records NRC Generic Letter 1995-071995-08-17017 August 1995 NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves NRC Generic Letter 1995-031995-04-28028 April 1995 NRC Generic Letter 1995-003: Circumferential Cracking of Steam Generator Tubes NRC Generic Letter 1995-041995-04-28028 April 1995 NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues NRC Generic Letter 1995-021995-04-26026 April 1995 NRC Generic Letter 1995-002: Use of Numarc/Epri Report TR-102348, Guideline on Licensing Digital Upgrades, in Determining the Acceptability of Performing Analog-To-Digital Replacements Under 10CFR 50.59 NRC Generic Letter 1995-011995-01-26026 January 1995 NRC Generic Letter 1995-001: NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities ML0312004431994-09-0202 September 1994 Withdrawn - NRC Generic Letter 1994-004: Voluntary Reporting of Additional Occupational Radiation Exposure Data NRC Generic Letter 1994-031994-07-25025 July 1994 NRC Generic Letter 1994-003: Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors NRC Generic Letter 1994-021994-07-11011 July 1994 NRC Generic Letter 1994-002: Long-Item Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors NRC Generic Letter 1994-011994-05-31031 May 1994 NRC Generic Letter 1994-001: Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators NRC Generic Letter 1993-081993-12-29029 December 1993 NRC Generic Letter 1993-008: Relocation of Technical Specification Tables of Instrument Response Time Limits NRC Generic Letter 1993-071993-12-28028 December 1993 NRC Generic Letter 1993-007: Modification of Technical Specification Administrative Control Requirements for Emergency & Security Plans NRC Generic Letter 1993-061993-10-25025 October 1993 NRC Generic Letter 1993-006: Research Results on Generic Safety Issue 106, Piping and the Use of Highly Combustible Gases in Vital Areas. NRC Generic Letter 1993-051993-09-27027 September 1993 NRC Generic Letter 1993-005: Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation NRC Generic Letter 1993-041993-06-21021 June 1993 NRC Generic Letter 1993-004: Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) NRC Generic Letter 1993-021993-03-23023 March 1993 NRC Generic Letter 1993-002: Public Workshop on Commercial Grade Procurement and Dedication NRC Generic Letter 1993-011993-03-0303 March 1993 NRC Generic Letter 1993-001: Emergency Response Data System Test Program NRC Generic Letter 1992-091992-12-31031 December 1992 NRC Generic Letter 1992-009: Limited Participation by NRC in IAEA International Nuclear Event Scale NRC Generic Letter 1992-081992-12-17017 December 1992 NRC Generic Letter 1992-008: Thermo-Lag 330-1 Fire Barriers NRC Generic Letter 1992-071992-10-20020 October 1992 NRC Generic Letter 1992-007 - Office of Nuclear Reactor Regulation Reorganization NRC Generic Letter 1983-281992-10-0707 October 1992 NRC Generic Letter 1983-028, Supplement 1: Required Actions Based on Generic Implications of Salem ATWS Events. ML0311304121992-09-16016 September 1992 Withdrawn NRC Generic Letter 1992-006 - Operator Licensing National Examination Schedule NRC Generic Letter 1992-051992-09-0404 September 1992 NRC Generic Letter 1992-005: NRC Workshop on the Systematic Assessment of Licensee Performance (SALP) Program 1999-08-23
[Table view] |
v-. an September
19, 1983 TO ALL OPERATING
REACTOR LICENSEES, APPLICANTS
FOR AN OPERATING
LICENSE AND HOLDERS OF CONSTRUCTION
PERMITS FOR BABCOCK & WILCOX PRESSURIZED
WATER REACTORS Gentlemen:
SUBJECT: SAFETY EVALUATION
OF "ABNORMAL
TRANSIENT
OPERATING
GUIDELINES" (GENERIC LETTER 83-31)The NRC staff has reviewed the proposed Oconee Nuclear Station, Unit 3 Abnormal Transient Operating Guidelines (ATOG) as described in Babcock &Wilcox (B&W) Owners Group letters dated March 31, 1982 and June 15, 1982, and D. Napiors letter from B&W to the Owners Group dated March 14, 1983.As discussed in the enclosed letter to the B&W Owners Group we have con-cluded that ATOG is acceptable as a basis for implementation of improved plant specific procedures and will provide improved guidance for operator emergency procedures over that which currently exists. Since there is no generic version of ATOG for B&W plants, the utilities who are participating in the Owners Group program are to provide sufficient documentation in the form of plant-specific ATOGs and Transient Information Documents (TIDs) so that the NRC can perform comparisons with the ATOG version evaluated in the enclosed Safety Evaluation Report (SER). We suggest that implementation of the guidelines proceed in 4 steps: (1) Interim extension of ATOG to better cover ATWS and certain aspects of natural circulation;
(2) Preparation of plant specific procedures which, in general, conform to the ATOG referenced above and implementation of these procedures as required by Generic Letter 82-33, dated December 17, 1982;(3) Preparation of supplements to the guidelines which cover changes, new equipment, or new knowledge and incorporation of these supplements into the procedures;
and (4) Completion and improvement of the guidelines to meet our long term requirements, followed by incorporation of improvements into plant specific procedures.
Step 1 is to be completed before ATOG is used in the implementation of procedures process. The prompt implementation of Step 2 will allow the benefits of the significant improvements you have achieved to be realized soon. We note however, that the guidelines are written for the procedure writers, not control room operators, and therefore, preparation and 830190 '5 Ef~Jt-2 Lf-Fl 8309190017
-2 -September
19, 1983 implementation of procedures will require additional Human Factors input.Step 3 refers to a program for guideline or procedure updates which will be generated as a matter of routine after the implementation.
This essentially is a maintenance function.
Step 4 refers to a program for addressing those aspects of the guidelines and procedures where additional long term work may be needed in your emergency procedure program.We have identified in the Safety Evaluation Report (SER) a number of items associated with the guidelines which need further work by the B&W Owners.We require that these items be addressed by either incorporating them into a future guideline revision or otherwise justifying the disposition of the item. The Owners Group letter of May 4, 1983 provided a satisfactory out-line of a plan to change the existing ATOG to a more generic document.
We share the Owners Group judgement that a B&W generic technical guideline will provide an effective mechanism for future guideline updates, changes and enhancements.
Additionally, because the Abnormal Transient Operating Guidelines must be dynamic in that changes must be made to reflect changes in equipment or new knowledge, we expect the B&W Owners' Group or a similar coalition of utilities and vendors to accept responsibility for continued maintenance of the guidelines.
Therefore, we have requested in the enclosed letter that the B&W Owners' Group provide a plan for addressing the SER items and a description of the program for steps 3 and 4 above.As discussed in the enclosed SER, the staff finds that ATOG represents a significant improvement over the guidance provided in current emergency operating procedures.
ATOG is symptom oriented, considers multiple failures, is tolerant of operator error, addresses plant cooldown following an emergency, and addresses inadequate core cooling. We find the approach used in ATOG to be responsive to the staff's criteria.
Further, ATOG contains a significant quantity of valuable information for the guidance of operators under emergency conditions.
The guidelines provide sufficient guidance such that they can be translated into acceptable emergency operating procedures using the process identified in NUREG-0899, "Guidelines for the Preparation of Emergency Operating Procedures." The staff therefore con-cludes that although efforts to improve the guidelines should continue, ATOG will provide a greater assurance of operational safety and are accept-able for implementation.
Sincerely, Darrell G. Eisenhut, Director Division of Licensing Enclosures:
'1. Letter to Mr. Whitney, dated 2 SER n Guidelines DL: i#5 DL:Q D j 'SA t DL R D JL oI:cc DCrui hfield F ,1i a I, /83 1/ 83 3 83
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